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Now store keff as an attribute in MGXS Library class

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wbinventor@gmail.com 2015-12-06 19:58:19 -05:00
parent ba959372f4
commit 510711e92f
1 changed files with 10 additions and 0 deletions
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10
openmc/mgxs/library.py
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@ -67,6 +67,9 @@ class Library(object):
sp_filename : str
The filename of the statepoint with tally data used to the
compute cross sections
keff : Real or None
The combined keff from the statepoint file with tally data used to
compute cross sections
name : str, optional
Name of the multi-group cross section library. Used as a label to
identify tallies in OpenMC 'tallies.xml' file.
@ -88,6 +91,7 @@ class Library(object):
self._tally_trigger = None
self._all_mgxs = OrderedDict()
self._sp_filename = None
self._keff = None
self.name = name
self.openmc_geometry = openmc_geometry
@ -114,6 +118,7 @@ class Library(object):
clone._tally_trigger = copy.deepcopy(self.tally_trigger, memo)
clone._all_mgxs = self.all_mgxs
clone._sp_filename = self._sp_filename
clone._keff = self._keff
clone._all_mgxs = OrderedDict()
for domain in self.domains:
@ -199,6 +204,10 @@ class Library(object):
def sp_filename(self):
return self._sp_filename
@property
def keff(self):
return self._keff
@openmc_geometry.setter
def openmc_geometry(self, openmc_geometry):
cv.check_type('openmc_geometry', openmc_geometry, openmc.Geometry)
@ -363,6 +372,7 @@ class Library(object):
self._sp_filename = statepoint._f.filename
self._openmc_geometry = statepoint.summary.openmc_geometry
self._keff = statepoint.k_combined[0]
# Load tallies for each MGXS for each domain and mgxs type
for domain in self.domains: